公开(公告)号：US4787979A

公开(公告)日：1988-11-29

申请号：US942401

申请日：1986-12-16

申请人： Zdenek Kolarik ,  Ulrich Galla ,  Klaus Roth

发明人： Zdenek Kolarik ,  Ulrich Galla ,  Klaus Roth

IPC分类号： B01D11/04 ,  G21C19/46

CPC分类号： B01D11/0492 ,  G21C19/46 ,  Y02W30/883

摘要： A liquid-liquid two-phase extraction process in which a feed solution is introduced into an intermediate stage of a multistage extraction apparatus. The solution is water and one or more valuable material to be recovered by extraction. An organic extractant is introduced into one end of the apparatus. The extractant is a solvent and flows through the apparatus. The valuable material is extracted from the feed solution to provide a charged organic phase. An aqueous extractant having water is introduced into another end of the apparatus to wash the charged organic phase. The aqueous extractant flows through the multistate extraction apparatus countercurrent to the extractant and contributes to the aqueous phase. The organic extractant is divided into at least two streams prior to introducing the organic extractant into the apparatus. Each stream is introduced into the apparatus at different stages, both ahead of the intermediate stage.

摘要翻译： 一种液 - 液两相萃取方法，其中将进料溶液引入多级萃取装置的中间级。 溶液是水和通过萃取回收的一种或多种有价值的材料。 将有机萃取剂引入装置的一端。 萃取剂是溶剂并流过该装置。 从进料溶液中提取有价值的材料以提供带电的有机相。 将具有水的水性萃取剂引入装置的另一端以洗涤带电的有机相。 水提取剂通过多提取提取装置与萃取剂逆流流动并有助于水相。 在将有机萃取剂引入装置之前，将有机萃取剂分成至少两股。 每个流在不同的阶段被引入到装置中，都在中间阶段之前。

公开(公告)号：US4758313A

公开(公告)日：1988-07-19

申请号：US685660

申请日：1984-12-24

申请人： Helmut Schmieder ,  Hans J. Bleyl ,  Zdenek Kolarik ,  Klaus Ebert

发明人： Helmut Schmieder ,  Hans J. Bleyl ,  Zdenek Kolarik ,  Klaus Ebert

IPC分类号： G21C19/46 ,  C25C3/34 ,  C01G43/00 ,  C01G56/00

CPC分类号： G21C19/46 ,  Y02W30/883

摘要： A process for the separation of substances hindering the recovery of the fissionable materials uranium and plutonium and for the separation of the fissionable materials to be recovered in a reprocessing process for spent, irradiated nuclear fuel- and/or fertile materials. A second and a third wash of the organic phase is performed for residual ruthenium separation and residual zirconium separation, and there is a repetition of the Pu stripping step with simultaneous electrolytic reduction of Pu(IV) to Pu(III). The second and third wash solutions or the aqueous phase employed for the repetition of plutonium stripping, respectively, each contains a high concentration of product uranyl nitrate. The aqueous run-off from the second and third washes and from the repetition of the Pu stripping step is indirectly fed back into the aqueous fuel solution employed in the first extraction step of the reprocessing method by first feeding these run-offs to an intermediate treatment.

摘要翻译： 分离妨碍可裂变材料铀和钚的回收的物质的分离过程，以及在废旧辐射的核燃料和/或肥沃材料的后处理过程中分离待回收的可裂变材料。 进行残留钌分离和残余锆分离的有机相的第二次和第三次洗涤，并且重复Pu剥离步骤，同时将Pu（IV）电解还原成Pu（III）。 分别用于重复钚汽提的第二和第三洗涤溶液或水相各自含有高浓度的硝酸铀酰产物。 从第二次和第三次洗涤出来的含水流出物和从Pu汽提步骤重复的含水流出物间接地反馈到后处理方法的第一提取步骤中使用的含水燃料溶液中，首先将这些排放物送入中间处理 。

公开(公告)号：US4839101A

公开(公告)日：1989-06-13

申请号：US7995

申请日：1987-01-29

申请人： Zdenek Kolarik ,  Robert Schuler

发明人： Zdenek Kolarik ,  Robert Schuler

IPC分类号： B01J20/02 ,  B01D11/04 ,  G21F9/00 ,  G21F9/12

CPC分类号： G21F9/12

摘要： The invention relates to a process for improving the effectiveness of the removal of zirconium from an aqueous, zirconium-containing nuclear fuel and/or fertile material solution in nitric acid in a liquid-liquid extraction process.Accordingly, the object of the invention is to improve the removal of zirconium from the reprocessing solutions and, at the same time, to simplify the course of the process. The invention seeks to improve decontamination of the uranium product and the plutonium product while, at the same time, reducing the outlay involved.According to the invention, this object is achieved in that, in a process step carried out before the first extraction of the nuclear fuels and/or fertile materials, the zirconium is converted from the dissolved state into a filterable or centrifugable solid phase by the use of an adsorbent from the group of inorganic ion exchangers and is removed from the aqueous solution together with the adsorbent.

摘要翻译： 本发明涉及一种在液 - 液萃取方法中提高从硝酸中含水的含锆核燃料和/或可育材料溶液中除去锆的有效性的方法。 因此，本发明的目的是改进从再处理溶液中除去锆，同时简化工艺过程。 本发明旨在改善铀产品和钚产品的去污染，同时减少所涉及的费用。 根据本发明，该目的的实现是，在第一次提取核燃料和/或可食材料之前进行的工艺步骤中，通过使用将锆从溶解状态转化为可过滤或可离心的固相 的来自无机离子交换剂组的吸附剂，并与吸附剂一起从水溶液中除去。

公开(公告)号：US4659551A

公开(公告)日：1987-04-21

申请号：US649009

申请日：1984-09-10

申请人： Zdenek Kolarik ,  Robert Schuler

发明人： Zdenek Kolarik ,  Robert Schuler

IPC分类号： C01G56/00 ,  C22B3/38 ,  C22B60/02 ,  G21C19/46

CPC分类号： C01G56/001 ,  C22B3/0044 ,  C22B3/0052 ,  C22B3/0066 ,  C22B3/0067 ,  C22B3/0068 ,  C22B60/026 ,  G21C19/46 ,  Y02P10/234 ,  Y02W30/883

摘要： A process for the separation of neptunium from an organic phase, which is developed in the recovery of irradiated nuclear fuel and/or fertile material. The organic phase contains uranium-, plutonium- and neptunium ions, tritium in the form of tritiated water and fission products in ionic form, as well as an organic extraction agent dissolved in diluent. After a first wash step, and before the organic phase is further fed to a uranium-plutonium separation or to a uranium-plutonium coreextraction, the organic phase is brought into contact with an aqueous solution containing diluted HNO.sub.3, butyraldehyde and a low concentration of sulfamic acid in countercurrent flow as a second wash step for the selective reduction of Np (VI) to Np (V) and for selective stripping of Np (V), with respect to U and Pu, from the organic into an aqueous phase. The resulting aqueous phase charged with Np (V) and with portions of tritium and fission products is brought into contact with a solution of fresh extraction agent solution having a flow which corresponds to from 1/13.3 to 1/3.3 of the flow of the organic phase coming from the first wash step and to be decontaminated, to assure the selectivity of the stripping of Np (V) in reference to U and Pu. The aqueous phase resulting from this step and containing Np (V), T and fission products is then separated from the solution of fresh extraction agent.

摘要翻译： 一种从有机相中分离ium的方法，该方法是在回收照射的核燃料和/或可食用材料时开发的。 有机相包含铀，钚和ium离子，以氚化水和离子形式的裂变产物形式的氚以及溶解在稀释剂中的有机萃取剂。 在第一洗涤步骤之后，在有机相进一步加入铀 - 钚分离或铀 - 钚冷萃取之前，将有机相与含有稀释的HNO 3，丁醛和低浓度氨基磺酸的水溶液接触 酸作为第二洗涤步骤，用于将Np（VI）选择性还原为Np（V），并将Np（V）相对于U和Pu从有机转化为水相。 将所得的带有Np（V）的水相和部分氚和裂变产物与新鲜萃取剂溶液的溶液接触，该溶液具有对应于有机物流的1 / 13.3至1 / 3.3的流量 相来自第一洗涤步骤并进行净化，以确保提取Np（V）的U和Pu的选择性。 从该步骤得到的含有Np（V），T和裂变产物的水相然后从新鲜提取剂的溶液中分离出来。